A method of decommissioning a nuclear facility including a plurality of sandboxes that cover a plurality of upper penetration holes, includes: exposing the plurality of pipes through the plurality of upper penetration holes by removing the plurality of sandboxes; and cutting the plurality of pipes through the plurality of upper penetration holes.

The invention relates to a method and an arrangement for operating a system in which dismantling works are performed underwater in a liquid-filled vessel (10) of a nuclear facility, the liquid being guided in a circuit (20) and flowing through at least one filter device (26, 28, 30). The liquid in the circuit flows through at least a first filter device (26) in the form of a coarse filter and a second filter device (28), in which at least one device from the group of ion exchangers (1, 2, 3), reverse osmosis systems, ultrafiltration systems, activated carbon filters, zeolite filters, and biological filters is used for filtration.

An apparatus for analyzing nuclides and the concentration thereof in waste contained in a radioactive waste packaging container according to the present disclosure relates to an apparatus that has detector devices located above/under the waste packaging container and performs nuclide and concentration analysis on the waste in the packaging container by scanning the packaging container in the longitudinal direction thereof using a forward/backward driving device. In particular, upper/lower detector modules are equipped with multiple high-resolution gamma ray detectors to increase inspection efficiency, each module is designed to be driven up/down, and each detector in the module is designed to be driven left/right, thereby performing nuclide and concentration analysis on various types of packaging containers regardless of the size thereof.

A method of decommissioning a nuclear facility, including: exposing the plurality of upper penetration holes by removing the plurality of sandboxes; enlarging an upper space of the cavity by cutting an upper portion of the biological shield concrete that is disposed between the plurality of upper penetration holes and between the plurality of upper penetration holes and the cavity; and separating the nuclear reactor pressure vessel from the biological shield concrete.

A method for decommissioning a nuclear facility includes: separating a nuclear reactor pressure vessel from biodegradable concrete; decommissioning a concrete structure; covering the biodegradable concrete; and decommissioning the biodegradable concrete.

A device for imaging radiation source in a decommissioning area of a nuclear power plant includes a detecting unit including a plurality of pixels for detecting an X-ray spectrum generated from a decommissioning area of a nuclear power plant, a processing unit connected to the detecting unit and configured to analyze the X-ray spectrum detected from the plurality of pixels and fuse a first element image displaying first pixels from which a first characteristic X-ray energy of a first element, among the plurality of pixels, is detected and a second element image displaying second pixels from which a second characteristic X-ray energy of a second element, among the plurality of pixels, is detected, into a fused image, and a display unit connected to the processing unit and configured to display the fused image corresponding to the decommissioning area.

An exposure dose measurement simulation device according to an embodiment of the present invention includes: a virtual work area generating portion that generates a virtual work area corresponding to a work area of a radiation facility; and an exposure dose prediction portion that predicts an exposure dose of a worker positioned in the virtual work area, wherein the exposure dose prediction portion includes a database portion that includes first data on a spatial dose rate of the radiation facility and second data on a position of a radiation source in the radiation facility, and a first exposure dose calculation portion that calculates the exposure dose of the worker positioned in the virtual work area using the first data and second data.

The invention proposes a tool and device, with the aid of which it is possible to remove the surface of walls, ceilings and floors also in the corners of contaminated interiors.

An apparatus for treating waste of a nuclear reactor pressure vessel includes: a suction unit inserted into the nuclear reactor pressure vessel through a plurality of through-pipes passing through a lower portion of the nuclear reactor pressure vessel to suck waste inside the nuclear reactor pressure vessel; a waste treatment part connected to the suction unit to treat the waste; and a lower collection part connected to the waste treatment part to be positioned under the nuclear reactor pressure vessel with the suction unit therebetween.

A method of handling spent nuclear fuel assemblies immerses the spent nuclear fuel assemblies in water in a relatively short time period when compared to traditional methods. A spent nuclear fuel assembly is removed from a nuclear reactor, an inert gas is applied to the fuel assembly, moisture content in the inert gas is gradually increased as it is applied to the fuel assembly, and the fuel assembly is immersed in water. The fuel assembly is immersed relatively quickly, within about 2 hours or less, which improves safety and allows normal processing and handling equipment to care for the fuel assembly. The fuel assembly may then be loaded into a cask for long-term storage and/or disposal.